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| Issue date | Title | Topic | |
|---|---|---|---|
| LD-88-005, Draft C-E Sys 80+TM Std Design, Design Certification Licensing Review Bases.Response to NRC Comments on Licensing Document Encl | 18 January 1988 | Draft C-E Sys 80+TM Std Design, Design Certification Licensing Review Bases.Response to NRC Comments on Licensing Document Encl | Mission time Probabilistic Risk Assessment Main transformer failure Earthquake Backfit Weak link |
| ML17223A697 | 30 April 1989 | Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46. | Fuel cladding |
| ML17297B168 | 31 December 1981 | Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Palo Verde 1,2 & 3 Reactor Vessels. | |
| ML17298B499 | 31 August 1984 | Errata to CEN-267(V)-NP & Rev 1-NP, Final Rept on Performance Evaluation of Palo Verde Control Element Assembly Shroud. | |
| ML17298B539 | 30 November 1984 | Summary Rept on Design Basis of Shutdown Cooling Sys Relief Valves for Cessar Sys 80. | Hydrostatic |
| ML17298B540 | 30 November 1984 | Summary Rept on Operability of Shutdown Cooling Sys Relief Valves for Palo Verde Units 1,2 & 3. | |
| ML17305A605 | 28 February 1990 | Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46, Suppl 1 | Fuel cladding |
| ML17305B514 | 30 April 1991 | Suppl 2 to, Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46. | Boric Acid Fuel cladding |
| ML17310B247 | 28 February 1994 | Nonproprietary Analysis of 137 Degree Capsule from APS Palo Verde Unit 2 Reactor Vessel Radiation Surveillance Program. | |
| ML17311B344 | 30 September 1995 | Safety Analysis Rept for Use of Advanced Zr Based Cladding Matl in PVNGS Unit 2 Batch J Demonstration Fuel Assemblies. | Fuel cladding |
| ML17346B171 | 31 July 1985 | Retran Code Transient Analysis Model Qualification. | Anticipated operational occurrence Fuel cladding Coast down |
| ML18113A771 | 31 October 1978 | Vepco Flame Model. Util Developed 3 Dimensional(X,Y,Z) Modified Diffusion Therory Calculational Model Designated as Vepco Flame Model.Accuracy of Model Is Demonstrated Through Comparisons Taken at Units 1 & 2 | |
| ML18139C061 | 4 October 1982 | Errata to VEPCO Reactor Core Thermal Hydraulic Analysis Using COBRA-IIIc/MIT Computer Code. | |
| ML18141A258 | 31 October 1983 | Revised Reactor Core Thermal-Hydraulic Analysis Using Cobra Iiic/Mit Computer Code. | Fuel cladding |
| ML18142A153 | 31 December 1984 | Nonproprietary Version of Revised VEPCO Evaluation of Control Rod Ejection Transient. | Shutdown Margin |
| ML18149A512 | 30 November 1986 | Qualification of WRB-1 CHF Correlation in VEPCO Cobra Code. | |
| ML19327C195 | 31 October 1989 | Nonproprietary Palo Verde Nuclear Generating Station-Unit 1 End-of-Cycle 2 Fuel Exam Rept. | |
| ML19351A419 | 30 September 1989 | Mark-BW Reload LOCA Analysis for Catawba & McGuire Units. | Boric Acid |
| ML20006A823 | 10 January 1990 | Errata to Rev 3 to BAW-1543, Master Integrated Reactor Vessel Surveillance Program Consisting of Revised Tables 3-20 & E-1 | |
| ML20024A921 | 30 June 1983 | Depressurization & Dhr,Response to NRC Questions. Executive Summary Included | |
| ML20040E789 | 31 January 1982 | to Class IE Qualification - Qualification of Class IE Electrical Equipment. | Safe Shutdown Safe Shutdown Earthquake Hydrostatic Design basis earthquake Earthquake |
| ML20052G584 | 14 May 1982 | Nonproprietary Statistical Combination of Uncertainties: Combination of Sys Parameter Uncertainties in Thermal Margin Analyses for Sys 80. | |
| ML20052H670 | 30 April 1982 | to Byron Units 1 & 2,Braidwood Units 1 & 2 Auxiliary Feedwater Sys Reliability Analysis, Final Rept | |
| ML20054L705 | 2 July 1982 | Nonproprietary Comprehensive Vibration Assessment Program for Prototype Sys 80 Reactor Internals,Palo Verde Nuclear Generating Station Unit 1 | Finite Element Analysis Earthquake Flow Induced Vibration |
| ML20062D617 | 1 July 1982 | Evaluation,Repair & Replacement of Damaged Internal Auxiliary Feedwater Header at Davis Besse 1,Oconee 3 & Rancho Seco | |
| ML20063C487 | 31 July 1982 | Errata & Addenda Sheet 7,replacing Pages 4-11 & 4-14 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations | |
| ML20069J554 | 30 September 1982 | Errata & Addenda Sheet 8,replacing Page 4-10 to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Stations | |
| ML20069K617 | 30 April 1983 | Revised Long-Term Iodine Control in Reactor Containment Bldg Using C-E Iodine Removal Sys | Boric Acid |
| ML20069P106 | 30 November 1982 | Nonproprietary Steam Generator Tube Plugging Margin Analysis for Westinghouse Snupps | Safe Shutdown Safe Shutdown Earthquake Flow Induced Vibration |
| ML20071E715 | 31 January 1983 | Core Protection Calculation & Control Element Assembly Calculator Data Base Document. Proprietary Info Deleted | |
| ML20072C013 | 28 February 1983 | Nonproprietary Sys 80 CESSAR FSAR Responses to Questions on Cesec | |
| ML20072K730 | 28 February 1983 | Evaluation of Small Break LOCA Operating Procedures & Effectiveness of Emergency Feedwater Spray for B&W-Designed Operating Nsss | |
| ML20078K336 | 30 September 1983 | VEPCO Nomad Code & Model | |
| ML20079Q903 | 24 January 1984 | Nonproprietary Rept on Palo Verde Unit 1 Safety Injection Nozzle Thermal Liner | Nondestructive Examination Finite Element Analysis Liquid penetrant |
| ML20080A757 | 31 January 1984 | Nonproprietary Interim Rept on Performance Evaluation of Palo Verde Control Element Assembly Shroud | Safe Shutdown Earthquake Operating Basis Earthquake Liquid penetrant |
| ML20080B495 | 29 July 1983 | Nonproprietary Version of Independent Evaluation of Proposed Mods to Westinghouse D4,D5 & E Steam Generators | Operating Basis Earthquake Nondestructive Examination Flow Induced Vibration |
| ML20081A121 | 30 September 1983 | Rev 1 to Suppl 3 of Probabilistic Risk Assessment of Effects of PORVs on Depressurization & Dhr | Probabilistic Risk Assessment |
| ML20082M885 | 31 October 1983 | Nonproprietary Version of VEPCO Evaluation of Control Rod Ejection Transient | Shutdown Margin |
| ML20083F050 | 30 November 1983 | Rev 1 to Leak Before Break Evaluation of Main Loop Piping of C-E Rcs | |
| ML20084H133 | 30 April 1984 | Vols 1 & 2 to Byron Generating Station Limiting Conditions for Operation Relaxation Program | Boric Acid Shutdown Margin Ultimate heat sink Mission time Probabilistic Risk Assessment |
| ML20091K902 | 29 February 1984 | Nonproprietary Technical Bases for Eliminating Large Primary Loop Pipe Ruptures as Structural Design Basis for Callaway & Wolf Creek Plants | Safe Shutdown Earthquake Pressure boundary leak |
| ML20092N576 | 30 June 1984 | Nonproprietary Technical Basis for Eliminating RHR Line Rupture as Structural Design Basis for Catawba Units 1 & 2 & McGuire Units 1 & 2 | Safe Shutdown Safe Shutdown Earthquake |
| ML20093N081 | 19 October 1984 | App a to Topical Rept DPC-NF-2010, Code Summary | FLEX |
| ML20094F632 | 31 July 1984 | Rev 0 to Calculation of Trip Setpoint Values,Plant Protection Sys | Backfit |
| ML20097J252 | 31 May 1984 | Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Byron Units 1 & 2 & Braidwood Units 1 & 2 | |
| ML20099K116 | 31 October 1975 | License Amend for Single-Loop Operation | Abnormal operational transient |
| ML20099K308 | 31 January 1976 | Suppl to Pilgrim Nuclear Power Station Unit 1 Amend for Single Loop Operation W/Bypass Holes Plugged | Abnormal operational transient |
| ML20100F096 | 30 November 1984 | Abnormal Transient Operating Guidelines (Atog) Comparison of Davis-Besse Unit 1 to Oconee Unit 3 | |
| ML20100J226 | 30 September 1984 | Rev 2 to Core Protection Calculation/Control Element Assembly Calculator Sys Phase I Software Verification Test Rept | |
| ML20100J254 | 30 September 1984 | Rev 2 to Core Protection Calculation/Control Element Assembly Calculator Sys Phase II Software Verification Test Rept |